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Radioactive Waste Disposal System Periodic Radiation Monitoring Survey. Core I, Seed 1. Test Results (T-612075). Section 2
Radiation levels were determined at all permanently installed monitored points in the disposal area. Radiation levels were found to be generally higher than those measured during the previous test but within Health Physics limitations. (J.R.D.)
Date:
October 1, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Gaseous Diffusion at Moderate Flow Rates in Circular Conduits
None
Date:
July 1, 1960
Creator:
Roley, G. & Fahien, R. W.
Object Type:
Report
System:
The UNT Digital Library
Nuclear Battery-Thermocouple Type Summary Report
The potential usefulness of approximately 1300 radioactive isotopes as a heat source for the thermoelectric generator was investigated. Only 47 were found to have the proper characteristics of high specific activity and usable haif-life combined with an easily absorbable radiation. These isotopes are discussed showing possible sources of supply, the hazards involved, and the expected performance. Three large Po/sup 210/ heat sources were designed and constructed (for battery use), including one for the SNAP III generator. One small Tl/sup 204/ test heat source was made by irradiation. Eight thermoelectric generators were developed and two of these were used as thermoelectric batteries. Theoretical equations for non-semiconductor thermoelectric materials and experimental measurements to verify the Thompson and Peltier effects are given. (auth)
Date:
October 1, 1960
Creator:
Blanke, B. C.; Birden, J. H.; Jordan, K. C. & Murphy, E. L.
Object Type:
Report
System:
The UNT Digital Library
Mass Transfer Coefficients and Interfacial Area in a One Stage Pulse Column
Over-all mass transfer coefficients were determined independently of the interfacial area by considering the operation of the pulse column to be a stage- wise process. The calculated coefficients describe only the operation of the pulse column for the free rise of organic droplets through a stage, since in the downstroke the aqueous phase passes through the organic phase in the form of rivulets preferentially wetting the plates. The driving force for transfer was based on the aqueous phase concentrations. The mass transfer coefficient was found to increase when the interfacial tension was reduced. Two factors appear to affect the mass transfer coefficient as the pulse frequency is changed and are: a) recycle or backmixing which tends to decrease the coefficient through a reduction of acetic acid in both phases and thereby increases the interfacial tension, and b) turbulence which enhances the coefficient by reducing the continuous film resistance. The first is important at or near the lower flooding limit, but the latter is the controlling factor at higher frequencies. (D.L.C.)
Date:
November 1, 1960
Creator:
Konopik, A. E. & Burkhart, L.
Object Type:
Report
System:
The UNT Digital Library
Determination of Aerodynamic Drag Parameters of Small Irregular Objects by Means of Drop Tests
Drag coefficients were determined for various irregular objects such as glass fragments, stones, steel fragments, and spheres by means of drop tests for use in a mathematical model to correlate nuclear explosion blast experiments. Drop tests were also made on small laboratory animals and extrapolated to estimate the drag properties of man. A method was developed to estimate the average drag properties of man from his total surface area. (D.L.C.)
Date:
June 1, 1960
Creator:
Fletcher, E. R.; Albright, R. W.; Goldizen, V. C. & Bowen, I. G.
Object Type:
Report
System:
The UNT Digital Library
Methods and Techniques of Fallout Studies Using a Particulate Simulant
The fallout hazard and protection factors in current use for large groups of buildings, i.e., urban residential areas, business districts, industrial complexes, government centers, Atomic Energy Commission facilities, and academic and medical institutions, are largely unsubstantiated by experimental evidence. These data are important for personnel protection on a national basis in the event of war and on a local basis in the event of certain types of nuclear accidents. The need for such information is discussed and methods for obtaining it are suggested. The methods suggested should provide a cross check of the data obtained on isolated structures under actual fallout conditions with the data from studies that made use of methods such as distributed point sources and a moving single-point source (as used in the Mobile Radiological Measurement Unit, Civil Effects Test Operations) to simulate actual fallout fields and with data from other studies in which predicted values of fallout protection were calculated from strictiy theoretical considerations. (auth)
Date:
August 1, 1960
Creator:
Lee, W. & Borella, H.M.
Object Type:
Report
System:
The UNT Digital Library
Zero Field Magnetic Properties of Gadolinium Terbium, and Samarium
The mutual inductance or apparent susceptibility due to the presence of the sample in a coaxial inductance coil was observed for Gd, Tb, and Sm in fields of a few gauss over the respective temperature ranges of 78 to 310 deg K, 78 to 235 deg K, and 4.2 to 150 deg K. A paramagnetic Curie point of 284.2 deg K was found for Gd. For Tb, a transition was found which occurred to within 1 deg of the predicted temperature of 220 deg K, and a second peak occurred at 229.4 deg K which is within 2 deg of the heat capacity peak. The 220 deg K peak exhibited hysteresis and time dependence. Extrapolation of Tb data to DELTA M = 0 yielded a Curie point of 235.6 deg K. No hysteresis was observed in the 14.8 deg K peak for Sm. (D.L.C.)
Date:
November 1, 1960
Creator:
Hill, E. D. & Spedding, F. H.
Object Type:
Report
System:
The UNT Digital Library
Thermal Expansion and Phase Inversion of Rare-Earth Oxides
Thermal expansion and phase inversion measurements are reported on oxides of Sc, Y, La, and 12 lanthanide series elements up to 1350 deg C. (J.R.D.)
Date:
October 1, 1960
Creator:
Stecura, S. & Campbell, W.J.
Object Type:
Report
System:
The UNT Digital Library
Research and Development of Metal Hydrides. Summary Report for October 1, 1958-September 30, 1960
A detailed study of the fundamental relations in the zirconium -- hydrogen system was made in order to clarify the many points of dispute and to evolve a complete picture describing all phases of this system. An engineering evaluation was made of means for utillzing the various high cross-section metal hydrides in shielding or control applications. These materials would combine the processes of thermalization and absorption. Consequently, they are of considerable interest for use in shielding or controlling epithermal reactors. (auth)
Date:
November 1, 1960
Creator:
Beck, R. L.
Object Type:
Report
System:
The UNT Digital Library
Equilibrium of the System Lanthanum Nitrate-Praseodymium Nitrate-Nitric Acid-Water-Tributyl Phosphate
A study of the extraction characteristics of the three systems lanthanum nitrate--nitric acid--water--tributyl phosphate, praseodymium nitrate--nitric acid--water--tributyl phosphate, and lanthanum nitrate--praseodymium nitrate nitric acid -water--tributyl phosphate was conducted. The separation factors between praseodymium and lanthanum for the system lanthanum nitrate--praseodymium nitrate-nitric acid--water--tributyl phosphate were shown to be a function of the total nitrate concentration of an equilibrium phase and practically independent of solute composition. A method of predicting the concentrations of lanthanum nitrate, praseodymium nitrate, and nitric acid in an equilibrium phase of the system lanthanum nitrate--praseodymium nitrate--nitric acid--water--tributyl phosphate was presented. A comparison of the extraction characteristics of the system rare-earth nitrate--nitric acid--water--tributyl phosphate for the nitrates of lanthanum, praseodymium, neodymium, and samarium was made. (auth)
Date:
November 1, 1960
Creator:
Sharp, B. M. & Smutz, M.
Object Type:
Report
System:
The UNT Digital Library
REACTOR THEORY DEVELOPMENT PROGRAM FOR ABWR. Annual Progress Report, October 1, 1959-September 30, 1960
None
Date:
January 1, 1960
Creator:
Newburg, E A & Noderer, L C
Object Type:
Report
System:
The UNT Digital Library
A METHOD OF EFFECTIVELY WIDENING THE BRAGG PEAK IN DEPTH IN THE PATH OF CHARGED HEAVY PARTICLES IN TISSUE
A device is described for the filtration of charged energetic heavy particles resulting in the production of adjacent or separated Bragg peaks within the range of the particles in tissue. Two or more layers of intense ionization at different depths separated by layers of less ionlzation in tissue can be produced. A cylinder of uniform ionization which cuts off sharply in depth in tissue can also be produced. (auth)
Date:
January 1, 1960
Creator:
Jansen, C.R.; Baker, C.; Calvo, W.; Rai, K.R. & Lippincott, S.
Object Type:
Report
System:
The UNT Digital Library
THE CRYSTAL STRUCTURE OF LiCuCl$sub 3$ /center dot/ 2H$sub 2$O
None
Date:
August 1, 1960
Creator:
Vossos, P. H.; Fitzwater, D. R. & Rundle, R. E.
Object Type:
Report
System:
The UNT Digital Library
Ionium, Uranium-232, and Thorium-228 Properties, Applications and Availability
Charts are given which present information on the properties, sources, and uses of Th/sup 230/, Th/sup 228/, and U/sup 232/ They also compare these properties with competitive isotopes. (M.C.G.)
Date:
August 1, 1960
Creator:
Rohrmann, C.A.
Object Type:
Report
System:
The UNT Digital Library
The Salt Cycle Process
The Salt Cycle Process is a nuclear fuel processing approach designed for application in compact facilities located at the reactor sites. Irradiated UO/sub 2/ fuels would be processed through a brief sequence of steps and partially purified UO/sub 2/ or UO/sub 2/--PuO/sub 2/ powders recovered, suitable for refabrication into fuel elements. The major steps of the process are the dissolution of uranium oxides in molten NaCl--KCl eutectic by chlorination to form soluble uranyl chloride and the reduction of uranyl chloride to UO/sub 2/, which separates as a solid. The preferred method of reduction is the electrolytic method, which yields UO/sub 2/ as a conveniently handled, adherent deposit on the cathode. Means are described for separation of Pu from U and for co-deposition of the Uo. Also included are discussions of the probable nature of the U and Pu species present in the molten salt, side reactions in which uranyl chloride may participate, and the influence of certain variables on the properties of the UO/sub 2/ produced. (auth)
Date:
August 1, 1960
Creator:
Benedict, G.E.; Lyon, W.L.; Mudge, L.K.; Swanson, J.L. & Walling, M.T. Jr.
Object Type:
Report
System:
The UNT Digital Library
Radiation Hazards Encountered in Arc Melting Thorium
A project to provide information on the hazards associated wlth arc melting of Th is described. A general airsampling analysis was made to determine the separation, concentration, and distribution of Th daughter (decay) products throughout arc melting, machining, and forging processes found in a handling facility. The value of well coordinated health physics program is stressed in connection with potential health hazards and personnel protection. Building, equipment, and exhaust ventilation requirements for such a facility are discussed, along wlth special handling methods. (auth)
Date:
November 1, 1960
Creator:
Lowery, R. R.
Object Type:
Report
System:
The UNT Digital Library
TEST OF GERMAN UNDERGROUND PERSONNEL SHELTERS
The predicted behavior of German underground personnel shelters, equipment, and certain instrumentation was investigated. Data obtained will be used for evaluation and improvement of present design criteria. Nine reinforcedconcrete underground shelters, designed by German engineers, were tested at the 170-, 155-, 110-, 78-, 26-, 11.5-, and 7.2-psi overpressure ranges as determined from average blast-line instrumentation measurements. Reinforcing steel, doors, and ventilation equipment were received and incorporated in the shelters. Preshot and postshot precise location surveys were made to determine the total lateral and vertical motions of the structure as a result of the blast. Blast instrumentation used in the shelters and entranceways consisted of pressure gauges, earthpressure gauges, self-recording pressure gauges, and dynamic pressure gauges. Free-field measurements were recorded along the blast line using U. S. self-recording and electronic pressure gauges and German self- recording pressure gauges. Structural response was recorded by deflection and acceleration gauges, strain gauges, and scratch gauges. Radiation measurements were taken using U. S. gamma-radiation film dosimeters, gamma-radiation chemical dosimeters, neutron detectors, telemetering gamma dosimeters, and German gamma chemical dosimeters. Mice were used as biological specimens in environmental tests in seven of the nine structures tested. In addition to the environmental tests, a series of tests …
Date:
July 1, 1960
Creator:
Cohen, E. & Bottenhofer, A.
Object Type:
Report
System:
The UNT Digital Library
Reactor Materials Study. Research and Development of Metal Hydrides. Quarterly Report No. 7 for April 1, 1960 to June 30, 1960
High-temperature x-ray diffraction experiments provided confirming evidence regarding the origin of the metastable gamma phase and of the general features of the zirconiumhydrogen phase system. These experiments also showed that the reaction alpha + delta -- beta (the eutectoid reactlon on heating) proceeds at an extraordinarily slow rate, although the reverse reaction proceeds so rapidly that beta phase cannot be retained to room temperature by quenching. The sluggishness of the eutectoid reaction on heating undoubtedly resulted in erroneous interpretation of certain physical and mechanical properties determined of the mechanical properties of zirconium hydride containing various minor alloy additions is continuing. Although these data are still quite sketchy, alloy additions of 5 at.% Sc or 2.2 at.% Cu show the most promise at this time. (auth)
Date:
July 1, 1960
Creator:
Beck, R. L.
Object Type:
Report
System:
The UNT Digital Library
REMOVAL OF A RADIOACTIVE PRIMARY SODIUM PUMP OR A RADIOACTIVE PRIMARY COLD TRAP
Methods and procedures are described for removing a radioactive primary sodium pump or a primary cold trap with handling casks from the Hallam Reactor. (D.L.C.)
Date:
May 1, 1960
Creator:
Mallon, P.J.
Object Type:
Report
System:
The UNT Digital Library
Laboratory Investigation of Decontaminating Solutions for Primary Loop Decontamination in the New Production Reactor
An investigation was made of methods for decontaminating the primary loop of the New Production Reactor (NPR). Decontamination factors ranging from fifty to several thousand were obtained with several different combinations of cleaning solutions. In general, fission product activity was removed to a lower residual level than was activated corrosion product activity, and carbon steel was easier to decontaminate than was stainless steel. It was necessary to completely remove the oxide film from the metal surfaces to obtain adequate activated corrosion product decontamination. Descaling procedures were also satisfactory for decontaminating fission product and uranium dioxide contamination. (M.C.G.)
Date:
November 1, 1960
Creator:
Mendel, J. E.
Object Type:
Report
System:
The UNT Digital Library
ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM. GCRE-I HAZARDS SUMMARY REPORT. ADDENDUM III
The hazards evaluation was modified to reflect certain changes made to the equipment as a result of operating experience. These changes included: the addition of a startup interlock circuit; the modification of a startup interlock circuit; several minor modifications to the control rod actuators; and the addition of the tube-sheet cooling system. (M.C.G.)
Date:
May 1, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
75,000 KILOWATTS OF ELECTRICITY BY NUCLEAR FISSION AT THE HALLAM NUCLEAR POWER FACILITY
For presentation at ASCE Convention in Reno, Nevada on Thursday, June 23, 1860. A description of the Hallam Nuclear Power Facslity is presented. The history of the project, program participants, site description, component development program, reaetor building, reactor structure, reactor core, sodium systems, instrumentation and control, fuel and component handling, auxsilary sustems, special design features, and advantages of sodium graphite reactor systems are discussed. (M.C.G.)
Date:
January 1, 1960
Creator:
Gronemeyer, F.C. & Merryman, J.W.
Object Type:
Report
System:
The UNT Digital Library
METAL-TO-CERAMIC SEAL TECHNOLOGY STUDY. Final Technical Report, June 22, 1959 to September 22, 1960
None
Date:
October 1, 1960
Creator:
Cole, S. S., Jr.; Larisch, W. L.; Inge, J. E.; Styhr, K. H., Jr. & Cheatham, E.
Object Type:
Report
System:
The UNT Digital Library
THERMAL DESIGN OF THE MGCR CORE
The design information is presented in sections on core thermal performance, fuel elements, moderator, and control rods. (J.R.D.)
Date:
August 1, 1960
Creator:
Rogers, J.T. & Katz, R.
Object Type:
Report
System:
The UNT Digital Library